NSTL国家科技图书文献中心

1. Design and characterisation of new low-alloyed alumina forming ferritic/ martensitic steels NSTL国家科技图书文献中心

F. Masari | Rebeca Hernandez ... - 《Materials Science & Engineering,A.Structural Materials: Properties, Misrostructure and Processing》 - 2025,922(Feb.) - 147598.1～147598.13 - 共13页

摘要： Forming Ferritic-Martensitic* steel, which combines the* | martensitic structure. Thermodynamic simulations guided the | New efficient energy generation systems | require materials capable of withstanding aggressive | environments. The Cr-rich oxides formed by commercial

关键词： Alumina-forming stainless steel | Ferritic-martensitic stainless steel | Spark plasma sintering | EBSD | Tensile strength | Small punch test | High-temperature oxidation

2. Advanced machine learning analysis of radiation hardening in reduced-activation ferritic/martensitic steels NSTL国家科技图书文献中心

Wang, Pengxin | Tao, Qing ... - 《Computational Materials Science》 - 2025,251 - 共11页

摘要： of reduced activation ferritic* martensitic (RAFM* | these features diminish and martensitic* laths recover* | This study uses advanced machine learning | models to investigate the radiation hardening behaviour | ) steels. An extensive dataset spanning nearly four

关键词： Reduced activation ferritic martensitic (RAFM) steels | Radiation hardening | Machine learning | GBDT | XGBoost | Random forest | Artificial neural network

3. Resistance to embrittlement in ferritic/martensitic steel with TaWVCr coating in oxygen-saturated lead-bismuth eutectic at 350 °C NSTL国家科技图书文献中心

Li, Shijiang | Tong, Zhenfeng ... - 《Surface & Coatings Technology》 - 2025,497 - 共13页 - 被引量：1

摘要：Ferritic/martensitic (F/M) steels are | potentially applied as structural materials in the lead | cooled fast reactor, a promising fourth-generation | reactor that adopts lead bismuth eutectic (LBE) as | coolant. However, the F/M steels normally suffer from a

关键词： Ferritic/martensitic steel | Complex concentrated alloy coating | Lead bismuth eutectic | Liquid metal embrittlement | Oxide cracks

4. Determining reference standard strength for neutron-irradiated reduced activation ferritic/martensitic steel F82H by Bayesian method NSTL国家科技图书文献中心

Nozawa, Takashi | Tanigawa, Hiroyasu ... - 《Journal of Nuclear Materials》 - 2025,604 - 共18页

摘要：The deterministic approach widely adopted in | the design of structural components relies on | systematically defined design limits using empirically | determined safety factors. However, this approach is not | always appropriate because structures are subjected to

关键词： Reduced activation ferritic/martensitic steel | Neutron irradiation | Tensile properties | Bayesian prediction

5. Effect of nickel on the hydrogen diffusion, trapping and embrittlement properties of tempered ferritic-martensitic dual-phase low alloy steels NSTL国家科技图书文献中心

Rodoni E. | Depover T.... - 《International journal of hydrogen energy》 - 2025,98(Jan.) - 418～428 - 共11页

摘要： using tempered dual-phase ferritic-martensitic* LAS* | © 2024Hydrogen embrittlement (HE) poses a | significant threat to hydrogen pipelines, which are | regulated by ASME B31.12 standard specifications. The | standard imposes a limit of 0.5 wt% nickel content in low

关键词： Dual-phase | Hydrogen embrittlement | Hydrogen permeation | Hydrogen transport | Slow strain rate tensile test

6. Microstructure evolution in ultra-high purity Fe-Cr alloys under low-PKA proton irradiation NSTL国家科技图书文献中心

Chen, Siwei | Li, Yao ... - 《Acta materialia》 - 2025,289 - 共13页

摘要：Fe-Cr based ferritic* steels are essential* | structural materials for nuclear reactor core applications | . This study investigates how Cr content and | irradiation temperature affect the formation of dislocation | loops and the chemical segregation in Fe-Cr binary

关键词： Ferritic-martensitic | Proton irradiation | Dislocation loop | Cr segregation

7. In-situ study on the differential evolution of He bubbles in the multilayer oxide of Fe9Cr1.5W0.4Si F/M steel corroded in lead-bismuth eutectic NSTL国家科技图书文献中心

Cui, Dewang | Cong, Shuo ... - 《Journal of Nuclear Materials》 - 2025,603 - 共13页

摘要：The combined effects of corrosion and | irradiation on nuclear components have been an important but | not yet fully revealed topic. Here, the irradiation | behavior of the oxide scale formed on F/M steel after | lead-bismuth corrosion was in-situ investigated

关键词： In-situ irradiation | Lead-bismuth corrosion | Oxide scale | He bubbles | Ferritic-martensitic steel

8. Configuration design and prototype development of a remote-centered parallel welding robot NSTL国家科技图书文献中心

Wen, Shikun | Qin, Guodong ... - 《Fusion engineering and design》 - 2025,211(Feb.) - 1.1～1.9 - 共9页

摘要：The vacuum chamber is one of the main | components of the fusion device, which is used to support | the internal components of the vacuum chamber and | the mechanical loads caused by its operation. The | vacuum chamber is generally processed by double-layer

关键词： Remote handling | Vacuum chamber | Parallel welding robot | Spiral theory | Special environment application | ACTIVATION FERRITIC/MARTENSITIC STEEL | VACUUM VESSEL | DISTORTION

9. Thermal mechanical evaluation of candidate tokamak divertor elements informing fusion materials design windows NSTL国家科技图书文献中心

Thomas, Spencer L. | Snead, Lance L.... - 《Fusion engineering and design》 - 2025,211(Feb.) - 1.1～1.16 - 共16页

摘要：Materials innovations represent a critical | need for future fusion pilot plants. Plasma facing | components (PFCs) used in the divertor will require | materials to operate continuously under harsh conditions | involving high heat loads and particle fluxes that act to

关键词： Fusion divertor | Computational fluid dynamics | Finite element analysis | Tungsten | Reduced activation ferritic martensitic steel | Copper chromium zirconium alloy | HELIUM-COOLED DIVERTOR | PURE TUNGSTEN | HEAT-TRANSFER | IRRADIATION...

10. Влияние скорости охлаждения на формирование структурно-текстурных состояний нержавеющей стали ферритно-мартенситного класса с 12%(масс.) хрома NSTL国家科技图书文献中心

В. И. ПАСТУХОВ | А Е. УСТИНОВ ... - 《Металловедение　и　термическая　обработка　металлов》 - 2025,(1 TN.835) - 3～12 - 共10页

摘要：Исследованы сформировавшиеся структурно | -текстурные состояния в образцах нержавеющей стали ферритно | -мартенситного класса, близкой по составу к Х12НМВСФБ, методом | сканирующей электронной микроскопии с использованием | ориентационного анализа и программного обеспечения по

关键词： нержавеющая ферритно-мартенситная сталь | γ → α-превращение | δ-феррит | мартенсит | сканирующая электронная микроскопия | ориентационная микроскопия | Stainless ferritic-martensitic steel | γ → α-transformation | δ-ferrite | Martensite...

摘要： Forming Ferritic-Martensitic steel, which combines the | martensitic structure. Thermodynamic simulations guided the | New efficient energy generation systems | require materials capable of withstanding aggressive | environments. The Cr-rich oxides formed by commercial

关键词： Alumina-forming stainless steel | Ferritic-martensitic stainless steel | Spark plasma sintering | EBSD | Tensile strength | Small punch test | High-temperature oxidation

摘要： of reduced activation ferritic martensitic (RAFM | these features diminish and martensitic laths recover | This study uses advanced machine learning | models to investigate the radiation hardening behaviour | ) steels. An extensive dataset spanning nearly four

关键词： Reduced activation ferritic martensitic (RAFM) steels | Radiation hardening | Machine learning | GBDT | XGBoost | Random forest | Artificial neural network

摘要：Ferritic/martensitic (F/M) steels are | potentially applied as structural materials in the lead | cooled fast reactor, a promising fourth-generation | reactor that adopts lead bismuth eutectic (LBE) as | coolant. However, the F/M steels normally suffer from a

关键词： Ferritic/martensitic steel | Complex concentrated alloy coating | Lead bismuth eutectic | Liquid metal embrittlement | Oxide cracks

摘要：The deterministic approach widely adopted in | the design of structural components relies on | systematically defined design limits using empirically | determined safety factors. However, this approach is not | always appropriate because structures are subjected to

关键词： Reduced activation ferritic/martensitic steel | Neutron irradiation | Tensile properties | Bayesian prediction

摘要： using tempered dual-phase ferritic-martensitic LAS | © 2024Hydrogen embrittlement (HE) poses a | significant threat to hydrogen pipelines, which are | regulated by ASME B31.12 standard specifications. The | standard imposes a limit of 0.5 wt% nickel content in low

关键词： Dual-phase | Hydrogen embrittlement | Hydrogen permeation | Hydrogen transport | Slow strain rate tensile test

摘要：Fe-Cr based ferritic steels are essential | structural materials for nuclear reactor core applications | . This study investigates how Cr content and | irradiation temperature affect the formation of dislocation | loops and the chemical segregation in Fe-Cr binary

关键词： Ferritic-martensitic | Proton irradiation | Dislocation loop | Cr segregation

摘要：The combined effects of corrosion and | irradiation on nuclear components have been an important but | not yet fully revealed topic. Here, the irradiation | behavior of the oxide scale formed on F/M steel after | lead-bismuth corrosion was in-situ investigated

关键词： In-situ irradiation | Lead-bismuth corrosion | Oxide scale | He bubbles | Ferritic-martensitic steel

摘要：The vacuum chamber is one of the main | components of the fusion device, which is used to support | the internal components of the vacuum chamber and | the mechanical loads caused by its operation. The | vacuum chamber is generally processed by double-layer

关键词： Remote handling | Vacuum chamber | Parallel welding robot | Spiral theory | Special environment application | ACTIVATION FERRITIC/MARTENSITIC STEEL | VACUUM VESSEL | DISTORTION

摘要：Materials innovations represent a critical | need for future fusion pilot plants. Plasma facing | components (PFCs) used in the divertor will require | materials to operate continuously under harsh conditions | involving high heat loads and particle fluxes that act to

关键词： Fusion divertor | Computational fluid dynamics | Finite element analysis | Tungsten | Reduced activation ferritic martensitic steel | Copper chromium zirconium alloy | HELIUM-COOLED DIVERTOR | PURE TUNGSTEN | HEAT-TRANSFER | IRRADIATION...

4008-161-200 800-990-8900

国家科技图书文献中心

摘要： Forming Ferritic-Martensitic* steel, which combines the* | martensitic structure. Thermodynamic simulations guided the | New efficient energy generation systems | require materials capable of withstanding aggressive | environments. The Cr-rich oxides formed by commercial

摘要： of reduced activation ferritic* martensitic (RAFM* | these features diminish and martensitic* laths recover* | This study uses advanced machine learning | models to investigate the radiation hardening behaviour | ) steels. An extensive dataset spanning nearly four

摘要： using tempered dual-phase ferritic-martensitic* LAS* | © 2024Hydrogen embrittlement (HE) poses a | significant threat to hydrogen pipelines, which are | regulated by ASME B31.12 standard specifications. The | standard imposes a limit of 0.5 wt% nickel content in low

摘要：Fe-Cr based ferritic* steels are essential* | structural materials for nuclear reactor core applications | . This study investigates how Cr content and | irradiation temperature affect the formation of dislocation | loops and the chemical segregation in Fe-Cr binary